JP2021527831A - Universal reversing reactor and design method and manufacturing of universal reversing reactor - Google Patents

Abstract

A fission reactor has a shell that encloses the reactor space in which a central longitudinal channel is contained, and a plurality of axially extending rings having adjacent rings are such that a first plurality of primary tubes are circumferential. Defines an annular cylindrical space arranged in the direction. Circumferentially adjacent primary tubing is separated by one of a plurality of secondary channels, and the plurality of webbings connect at least a portion of the plurality of primary tubing to adjacent structures. The fissile nuclear fuel composition is located in at least some of the plurality of secondary channels and the primary coolant passes through at least some of the primary shaft tubes. Laminated molding and subtractive manufacturing techniques produce an integral structure and a single structure of fuel-filled reactor space. Reactor designs in production and at completion can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during production.

Description

Related Applications This application is filed on June 21, 2018 for US Provisional Patent Application Nos. 62 / 688,255. S. C. § 119 (e) claims priority, the entire contents of which are incorporated herein by reference.

The present disclosure generally relates to fission reactors and structures related to active reactor space within fission reactors. In particular, the disclosed fission reactors and reactor space contain fissile nuclear fuel loaded into the space between channels for coolant flow, and while being expandable in size, regardless of reactor size. Each location with fissionable nuclear fuel remains the same in cross-sectional area and / or volume. Support and auxiliary equipment such as control rods, control rod drivers, moderators, etc. can be expanded in size. The present disclosure also relates, in particular, to methods of manufacturing such reactors and structures by laminated molding techniques that produce integral and single structures for fuel-loaded reactor spaces, such reactors and Provides predictive quality assurance for the manufacture of structures.

The following description refers to specific structures and / or methods. However, the following references should not be construed as acknowledging that these structures and / or methods constitute prior art. Applicant expressly reserves the right to demonstrate that such structures and / or methods are not qualified as prior art for the present invention.

Conventional fission reactors utilize fissionable nuclear fuel, such as uranium-based fuel, by placing it inside a round tube, plate, or hexagonal fuel element. These fuel elements are collected and placed in the fuel assembly, which is the basic element of the core of a nuclear reactor. Conventional fuel assemblies 10 (see FIG. 1) include, for example, fuel elements 12 (including fuel 14 and flammable toxins), mechanical support of the fuel assembly structure, spacer grid 16 (component spacing and fuel elements). A complex arrangement of non-fuel pipes for, for example, control rods 18 or in-core instrumentation 20). Depending on the design, the reactor vessel may have dozens of fuel assemblies (also known as fuel bundles), each assembly 10 may contain more than 200 fuel elements 12.

In the core, the primary coolant (such as water) flows through and / or around the fuel assembly 10 and is produced by the fission reaction moderator (in the case of a water-based cooling reactor) and the fission reaction in the fuel element. Both provide a heat extraction medium for the heat to be generated. The heated primary coolant circulates within the primary cycle (meaning a system that is exposed, contacted, or exposed to the primary coolant), traditionally transferring heat energy to the secondary system where heat is generated. Excited fluid is generated and flows into the turbine, which can be used to rotate the generator.

Structural complexity extends to other systems in the reactor, including various components of the primary cycle, such as tubes, pumps, instrumentation, heat exchangers, steam generators, etc., depending on the design. Therefore, the construction of fuel elements, fuel assemblies, cores, and reactor systems are all pre-manufacturing and in-manufacturing, including those related to procurement, handling, installation, inspection and testing, in addition to strict design and manufacturing standards. , And are subject to extensive post-manufacturing control.

Therefore, designing these complex structures, especially fuel elements and fuel assemblies, would be advantageous in improving either the design and manufacture of such complex structures and quality assurance.

In general, the present disclosure relates to fission reactors in which fissile nuclear fuel is placed between and around non-fuel pipes for primary coolants, moderators, control rods, scram rods and / or auxiliary devices. This arrangement of fissile nuclear fuel and non-fuel pipes is the opposite (or vice versa) of the conventional arrangement of primary coolant flowing between and around the fissile fuel and fuel pipes placed in the pipe.

The embodiments disclosed herein include a shell comprising a reactor space having a longitudinal axis and an inner diameter surface defining a central longitudinal channel having an axis co-located with the longitudinal axis of the reactor space. Includes a fission reactor with an axial cylinder including. A plurality of axially extending rings are arranged in the reactor space and are arranged concentrically with respect to the axial cylinder. The plurality of axially extending rings are radially separated to form both a ring adjacent radially inward and a ring adjacent radially outward for any two adjacent axially extending rings. The outer diameter surface of the ring adjacent to the inner side in the radial direction and the inner diameter surface of the ring adjacent to the outer side in the radial direction define an annular cylindrical space. The fission reactor includes a first plurality of primary shaft tubes arranged in the circumferential direction in each annular cylindrical space. Each primary shaft contains an inner diameter surface and an outer diameter surface that form the primary channel. In the plurality of webbings, at least a part or all of the plurality of primary shaft tubes is connected to the ring adjacent to the radial inner side by the first webbing, and to the ring adjacent to the radial outer side by the second webbing. Connect to adjacent structures such as the outer diameter surface of each of the plurality of primary shaft tubes. The fission reactor contains a plurality of secondary channels in each annular cylindrical space, and the circumferentially adjacent primary shaft tubes are separated by one of the plurality of secondary channels. The fissile nuclear fuel composition is located in at least some of the multiple secondary channels.

The embodiments disclosed herein also include methods of making a fission reactor. Embodiments of this method apply predictive and causal analysis to prepare a model of the fission reactor and apply stacking techniques during the production of in-situ monitoring manufacturing of the fission reactor with mechanical vision and accelerated data processing. It is used to build a fission reactor layer by layer, analyze data from in-situ monitoring, and coordinate fission reactor production based on the data analyzed in real time. In some cases, the production volume of manufacturing equipment, especially laminated molding equipment, is limited and affects the maximum size of a single monolithically manufactured part (however, relocation technology makes such monolithic manufacturing. May accommodate increased component size). Thus, for example, the manufacturing methods disclosed herein for fission reactors (or other structures) can be adapted to manufacture structures on a monolithic or segment basis for subsequent assembly.

An embodiment of this method can also prepare a digital version of the manufactured fission reactor. Then, based on the analysis of the digital version of the manufactured fission reactor, the characteristics of the manufactured fission reactor are correlated.

In addition, the embodiments disclosed herein can be used to authorize the design of a fission reactor, to make acceptable manufacturing, and to verify the individual components of the fission reactor. For example, the methods of manufacturing fission reactors disclosed herein can also be used to determine and confirm the performance and integrity of the structure as it is completed. Therefore, these methods can serve as a new means for providing information on reactor accreditation or acceptance criteria by third parties, such as government regulators, government agencies and departments, and commercial organizations such as power companies. can.

The disclosed reactors and cores have complex mechanical shapes, such as 3D printing of elemental metals or metal alloys or ceramics, including the use of such materials in the form of particles, wires or powders. Body shape and repetitive manufacturing can make reversing reactors easier to build. Other benefits include improved weight output ratios, reduced internal stresses, and expandability, for example by adding additional dimensional units in the form of rings or ring spacing.

The above summary, as well as the following detailed description of the embodiments, can be better understood when read in conjunction with the accompanying drawings. It should be understood that the illustrated embodiments are not limited to the exact arrangement and means shown.

It represents a conventional fuel assembly with fissionable nuclear fuel and non-fuel pipe rods with fuel elements in which the primary coolant flows in and / or around it. A perspective axial sectional view of an exemplary fission reactor is shown. An enlarged perspective radial cross section of an exemplary shell surrounding the reactor space is shown. A cross-sectional view in the radial direction of a part of the fission reactor is shown. FIG. 3A shows a partial enlarged perspective radial cross-sectional view of FIG. 3A. A perspective radial cross-sectional view and an axial cross-sectional view of an example of a part of a fission reactor and a fuel element are shown. FIG. 3 is a schematic perspective view showing support and auxiliary devices arranged in a plurality of primary channels. An example of a neutron deceleration material in the form of a rod is shown. An example of a neutron deceleration material in the form of a rod is shown. FIG. 3 is a schematic perspective view showing the control rod system and its position relative to a partially clipped view of the fission reactor. An exemplary number and distribution of control rods and moderators in an exemplary embodiment of a fission reactor is shown in a perspective cross section. FIG. 6 is a schematic diagram showing a portion of a radial cross section of an exemplary embodiment of a fission reactor incorporating spaces or gaps to reduce the stress resulting from the transmutation of elements due to fission of fissile nuclear fuel. It shows the 6-fold rotational symmetry of an exemplary embodiment of the disclosed fission reactor. It summarizes the embodiments of additive manufacturing for the production of integral and single structures for fission reactor and fuel loaded reactor spaces disclosed herein. Shown are screenshots related to aspects of the Universal Inversion Reactor Computation Platform (“UIRCP”) used to investigate aspects of a fission reactor embodiment. Shown are screenshots related to aspects of the Universal Inversion Reactor Computation Platform (“UIRCP”) used to investigate aspects of a fission reactor embodiment. Details of the geometric structure and dimensions of the geometrically related variables used in Example 2 are shown. Details of the geometric structure and dimensions of the geometrically related variables used in Example 2 are shown. An example of a solid CAD model obtained from the universal reversal reactor computing platform process of Example 2 is shown. It is an example of the temperature contour diagram obtained from the universal reversal reactor calculation platform process of Example 2. The temperature and neutron engineering profiles associated with exemplary embodiments of the fission reactor are shown. The temperature and neutron engineering profiles associated with exemplary embodiments of the fission reactor are shown. The temperature and neutron engineering profiles associated with exemplary embodiments of the fission reactor are shown.

FIG. 2A shows a perspective axial sectional view of an exemplary fission reactor. The fission reactor 100 includes a shell 102 containing a fissile nuclear fuel composition (an example of which is shown as a fissionable nuclear fuel composition 104 in FIG. 2B), a control rod and a control rod that movably penetrates the reactor space. It includes an auxiliary device 106, a reflector 110 around the outer diameter surface of the shell 102, a tube for the flow 112 of the primary coolant in and out of the shell 102, and a storage container 114. FIG. 2B shows an enlarged perspective view, a radial cross section and an axial cross section of some of the features of FIG. 2A. For illustration and clarification, other features of the fission reactor and fission power plant, such as other features of the primary and secondary systems, are not shown in FIGS. 2A-2B but are known to those of skill in the art. ing.

FIG. 3A shows a cross-sectional view in the radial direction of a part of the fission reactor 100. The illustrated shell 102 has a longitudinal axis 120 extending from the first end to the second end of the reactor space 108. In this embodiment, the shell 102 includes a reactor space 108 having internal features similar to a honeycomb structure, both in the radial and axial directions. For example, within the shell 102 is an axial cylinder 130 that includes an inner diameter surface 132 that defines a central longitudinal channel with an axis 134 co-located with the longitudinal axis 120 of the reactor space 108.

Further, in the reactor space 108, a plurality of axially extending rings 140 arranged concentrically with respect to the axial cylinder 130 are arranged. With reference to FIG. 3B, an enlarged radial cross-sectional view of a portion of FIG. 3A is shown. At least some of the plurality of axially extending rings 140 are radially separated, and if any two axially extending rings 140 are considered, the ring 140a adjacent radially inward and adjacent to the radial outer side. Ring 140b is formed. The outer diameter surface 142 of the ring 140a adjacent to the inner side in the radial direction and the inner diameter surface 144 of the ring 140b adjacent to the outer side in the radial direction define the cylindrical space 150.

Arranged in the circumferential direction in the annular cylindrical space 150, there are a plurality of primary shaft tubes 160. Each primary shaft tube 160 includes a primary channel 164 (mainly used for flow) and an inner diameter surface 162 forming an outer diameter surface 166. The plurality of webbing 170s each of the outer diameter surfaces 166 of the plurality of primary shaft tubes 160 are adjacent to the ring 140a adjacent to the inner side in the radial direction in the first example, and to the ring 140a adjacent to the outer side in the radial direction in the second example. Connect to 140b. In some embodiments, the shaft tube 160 is connected by a webbing 170 to at least one or both of a ring 140a adjacent radially inward and a ring 140b adjacent radially outward. In another embodiment, only a portion of the shaft tube 160 is connected by a webbing 170 to at least one or both of a ring 140a adjacent radially inward and a ring 140b adjacent radially outward. The number, location, and frequency of use of the webbing 170 can vary based on the dimensional integrity provided for the overall design by making connections using the webbing 170.

The inner diameter surface of the primary shaft tube (ie, the primary flow channel) can be uniform or variable as a function of axial position. For example, in some embodiments, the inner diameter surface of the primary shaft tube forming the primary channel is, for example, a function of the axial position of the primary shaft tube with respect to the longitudinal axis to affect the flow characteristics of the primary coolant. Can change. Also, for example, in other embodiments, the primary channels are chambered to form different regions or zones along their axial lengths. These zones can be used to house equipment and / or other equipment or materials for monitoring or influencing the performance of the reactor.

In some embodiments, one or more of the central longitudinal channels and primary channels 164 of the axial cylinder 130 are accessible from the outer surface of the fission reactor. Where accessible, central longitudinal channels and / or primary channels can be used to prepare irradiated samples such as irradiated medical devices, medical isotopes, and scientific isotopes.

Further, a plurality of secondary channels 180 are arranged in the reactor space 108. Referring to FIG. 3B, the plurality of secondary channels 180 are arranged in the annular cylindrical space 150 and separate the primary shaft tubes 160a and 160b adjacent in the circumferential direction. For example, the inner surface of the secondary channel 180 is a portion of the outer diameter surface 166 of the primary shaft tubes 160a and 160b adjacent in the circumferential direction, and the first related to the primary shaft tubes 160a and 160b adjacent in the circumferential direction, respectively. Includes the surfaces of the webbing 170 and the second webbing 170, a portion of the outer diameter surface 142 of the ring 140a adjacent radially inward, and a portion of the inner diameter surface 144 of the ring 140b adjacent radially outward. Typically, the primary shaft tubes 160a and 160b adjacent to each other in the circumferential direction are non-contactly distributed in the cylindrical space 150 to form the secondary channel 180.

Further, a fissile nuclear fuel composition 190 is arranged in the reactor space 108. For example, as outlined in FIG. 4, the fissile nuclear fuel composition 190 can be located in at least some of the plurality of secondary channels 180. The fissile nuclear fuel composition 190 is in heat transfer contact with at least some, if not all, of the inner surface of the secondary channel 180. During operation, the primary coolant is in each of the circumferentially adjacent primary shaft tubes 160 separated by one of a plurality of secondary channels 180 containing the fissile nuclear fuel composition 190 to provide heat transfer. It can flow through the primary channel 164. In the illustrated embodiment, the cross section of the secondary channel perpendicular to the longitudinal axis has the shape of a single hyperboloid cross section, but other cross-sectional shapes can be used. Suitable fissile nuclear fuel compositions include uranium oxide, less than 20% enrichment, 10% by weight molybdenum uranium (U-10Mo), uranium nitride (UN), and metal-based fissile fuels and Includes other stable fissile fuel compounds, including ceramic-based fissile fuels.

As is known in the art, during the fission reaction of fissile nuclear fuel, the decomposition of uranium produces many alternative elements in different phases (gas, liquid, or solid). Due to the design of the secondary channel 180 containing the fissile nuclear fuel composition 190 disclosed herein, the increase in internal pressure within the secondary channel 180 due to this transmutation of the element causes the secondary channel 180, i.e. the fuel chamber. Place it in compressive force to improve resistance to failure. This phenomenon is also seen when thermal expansion occurs. In contrast, in conventional reactor fuels, where uranium is usually placed in a tube made of zirconium, transmutation of the elements increases the pressure inside the tube, causing hoop stress (a type of tensile hoop stress) in the tube. , Can lead to structural damage such as cracks. Also, materials that are subject to tensile stress are more susceptible to various types of corrosion mechanisms, such as stress corrosion cracking, than materials that are subject to compressive stress. Furthermore, hydride-forming metals (such as zirconium) are susceptible to hydrogen embrittlement and can be brittle and fracture. This is exacerbated when the associated part is under tensile stress compared to compressive stress.

Note that in the illustrated embodiment of FIG. 3A, the innermost primary axles are not separated from the axial cylinder 130 by an axially extending ring 140. Therefore, the reactor 100 includes a plurality of primary shaft tubes 160 arranged in the circumferential direction between the inner diameter surface of the ring 140 extending in the innermost radial direction and the outer diameter surface of the axial cylinder 130. The outer diameter surface of each of these plurality of primary shaft tubes is connected to the outer diameter surface of the axial cylinder 130 by the first webbing 170, and the second webbing is similar to that described in connection with FIG. 3B. The 170 connects to a ring 140 that extends in the innermost radial direction.

It should also be noted that in the illustrated embodiment of FIG. 3A, the outermost primary axles are not separated from the shell 102 by an axially extending ring 140. Therefore, the reactor 100 includes a plurality of primary shaft tubes 160 arranged in the circumferential direction between the inner diameter surface of the shell 102 and the outer diameter surface of the ring 140 extending in the outermost radial direction in the axial direction. As described in connection with FIG. 3B, the outer diameter surface of each of these plurality of primary shaft tubes is connected to the outer diameter surface of the ring 140 which extends axially outward most radially by the first webbing. And connected to the inner diameter surface of the shell 102 by a second webbing.

Various supports and auxiliary devices can be arranged in one or more primary channels 164. For example, moderators, control rods, and at least one of scientific instruments such as temperature sensors or radiation detectors can be placed in one or more primary channels. FIG. 5A is a schematic view of a plurality of primary channels 164 in which a support and auxiliary device in the form of a control rod 200 such as an iridium control rod and a moderator 210 such as a zirconium hydride neutron moderator are arranged. Control rods 200 can also incorporate neutron poisons that can be used to absorb neutrons and regulate the criticality of the reactor. In addition, the toxicant can absorb enough neutrons to shut down the fission reactor 100 (eg, when the control rods 200 are fully inserted into the reactor space 108) or the criticality of the fission reactor 100. It can be arranged axially to maintain (eg, when control rods 200 are pulled out a distance from the core 109 to allow a continuous fission chain reaction). In some embodiments, the moderator 210 is cooled by flowing He and stabilized in a tri-fin design. Appropriately distributed throughout the reactor space 108 to obtain one or more of the desired flux profile, power distribution, and operating profile using any suitable number of control rods 200 and moderator 210. can do. In an exemplary embodiment, the control rods 200 are threaded, which contributes to saving axial space, maximizes control rod diameters, and into roller nuts for reliable SCRAM operation. Allows direct contact. All or a subset of control rods 200 can be individually controlled by independent motors to provide individual reactivity control and / or for power forming.

In some embodiments, inserts of neutron deceleration material in the form of rods with one or more axial protrusions can be placed in the primary channel 164. 5A and 5B show examples of such neutron deceleration materials in the form of rod 210 within the primary channel 164. The rod 210 is one or more fins 212 or the other that contribute to maintaining a consistent gap 214 between the inner diameter surface of the primary channel 164 and the outer surface (or at least most of the outer surface) of the moderator rod 210. Includes protrusions. The fins / protrusions 212 can extend axially along the length of the rod 210. This design is especially for gas-cooled reactors where the gap 214, for example, produces thrust in a space reactor or drives a closed-loop power generation system, allowing sufficient flow of gas to cool the deceleration material. Related. The deceleration material also acts to heat the neutrons, creating a more neutral and efficient core.

The individual moderator rods can be advantageously inserted in any number of desired positions within the core and can be replaced or serviced independently as needed for large diameter cooling during core manufacturing. Allows material holes.

The moderator rod 210 is also as shown in an alternative embodiment of the moderator rod 210 shown in FIG. 5C to allow additional cooling or to accommodate the insertion of control rod 200 or other material. It can take the form of a ring. A coating can also be used on the hydride to limit or prevent the transfer of hydrogen, an important component of neutron deceleration from metals. The coating process can also be used as a barrier between the deceleration material and the cooling gas.

As mentioned in the discussion of FIG. 2A, the fission reactor 100 includes control rods that movably penetrate the shell 102 and the reactor space 108. The positioning and operation of control rods such as control rod 200 is controlled by control rod system 220 (see FIG. 5D). Embodiments of control rod system 220 include three main items. A control rod drive motor 230 used to move the control rods 200 in and out of the reactor space 108. A screwed drive shaft 240 connected to the control rods 200 for moving the control rods 200 in and out of the reactor space 108. Control rod 200, which is a cylindrical neutron absorbing poison that normally enters and exits the primary channel 164. Moving the control rods 200 in and out of the reactor space 108 is usually located inside the control rod drive motors, rotating the threaded nuts coupled to the threaded drive shafts, and the rotation of the threaded nuts translates. That is, it is done by causing the control rod 200 to move in the longitudinal direction.

In some applications, such as space reactors, the size and weight of fission reactors and their components are limited to the weight / cost disadvantages that occur when such systems are launched into space. Therefore, other embodiments of control rod systems seek to simplify their design, as maintenance or replacement of reactor components cannot be performed once activated or activated. Therefore, it is beneficial to reduce the size, weight, and complexity of items within the control rod system. Although not necessarily limited in size and weight, ground reactors can benefit from similar design improvements through reduced maintenance and reduced parts replacement. To address such design concerns, control rod system embodiments can combine a threaded drive shaft with a control rod venom by manufacturing the threaded drive shaft itself from a neutron absorbing material. If the threaded drive shaft is manufactured using neutron absorbing material, individual control rod venom can be reduced or eliminated from the fission reactor.

The control rod 200 of FIG. 5A illustrates an exemplary embodiment of such a threaded control rod manufactured from a neutron absorbing material or otherwise incorporated into its structure. Suitable materials that can be used (or incorporated into the structure) in the manufacture of control rods include iridium, hafnium, tantalum, tungsten, boron carbide in aluminum oxide matrix (Al ₂ O _3- B ₄ C), Includes molybdenum and tantalum. Although any one or more of the various hot metal neutron absorbing materials can be used, it is currently contemplated that iridium will be used as the neutron absorbing material.

FIG. 6 is a perspective cross-sectional view showing an exemplary number and distribution of control rods 200 and moderator 210 in an exemplary embodiment of a fission reactor.

As discussed above, transmutation of elements increases the internal pressure associated with the space occupied by fissile nuclear fuel. To reduce such internal pressure, fission reactor embodiments can be designed with flexibility in the fission reactor components to reduce the stresses generated. For example, instead of a continuous volume of fuel, the disclosed fission reactor embodiments include spaces, gaps, holes or spaces between sections of the fissile nuclear fuel composition within the secondary channel 180 or within the fissile nuclear fuel composition 190 itself. Other openings can be incorporated. An example of such a space or gap is shown in FIG. 7, where one or more gaps 250 are incorporated into the fissile nuclear fuel composition 190. Examples of the location of the gap 250 include between the fissile nuclear fuel composition 190 and the webbing 170 (see region 252) and within the body of the fissile nuclear fuel composition 190 (see region 254). Modeling of stresses in the gap-incorporated design showed lower stresses in the active reactor space 108 in the gap region compared to the non-gap region. In addition, the overall hoop stress of the shell 102 has been reduced. In addition, the fissile nuclear fuel composition 190 showed a better interface with the surface and structure forming the secondary channel 180, resulting in better heat transfer performance. For example, incorporating the gap 250 into the design has been shown to improve contact with each outer diameter surface 166 of the plurality of primary shaft tubes 160 (compared to designs without such a gap 250). This contributes to improved heat transfer between the fissile nuclear fuel composition 190 and the primary coolant flowing through the primary channel 164 formed by the inner diameter surface 162 of the primary shaft tube 160.

In some embodiments, the fission reactor 100 is the core of a gas-cooled reactor and the heat transfer is sized to allow efficient heat transfer from the solid core, FIGS. 3A-3B. , 4 and 5A, through the gas flowing through the holes in the reactor space 108, such as the primary channel 164. In a gas-cooled reactor embodiment, the primary coolant removes heat from the core, which in turn heats the gas. The heated gas can be used for thrust, such as a nuclear thermal rocket, or for driving a closed-loop power generation system. To generate heat in the fissile nuclear fuel transferred to the primary coolant, the reactor relies on neutron moderators to heat or slow down the neutrons emitted during the fission process. Neutron deceleration is required to maintain the nuclear chain reaction in the core and thus the generation of heat. Water-cooled reactors rely on water to cool and slow down neutron populations. However, gas-cooled reactors require additional material for deceleration. The use of additional moderators to heat the neutrons can reduce the amount of fuel and thus the weight of the fission reactor, as the heated neutrons divide the fissile atoms more efficiently.

In some embodiments, a fission reactor characterized by at least a shell, an axial cylinder, a plurality of axial rings, a plurality of primary shaft tubes, and a plurality of webbings is a single structure. In other words, these features of the fission reactor are integrally formed, for example, by a stacking process. An example of a suitable laminated molding process utilizes 3D printing of a metal alloy containing molybdenum, a metal alloy such as Zircaloy-4 or Hastelloy X, to form a structural feature of interest. In other embodiments, the fissile nuclear fuel composition can be included within an integrated single structure if a suitable multi-material laminate molding process using multiple metals in the raw material is used. Other alloys that can be used when adopting a suitable multi-material laminate molding process that uses multiple metals in the raw material are steel alloys, zirconium alloys, and molybdenum-tungsten alloys (for shells), berylium alloys (for reflectors). ), And stainless steel (for storage containers). Powdered raw materials are also available.

The reactors shown and described herein have six rotational symmetry with respect to the longitudinal axis of the reactor space. For example, referring to FIG. 8, it can be seen that similar features within the reactor space 108 are arranged six times rotationally symmetric with respect to the longitudinal axis 120 of the reactor space. An example of this 6-fold rotational symmetry is shown in FIG. 8 superimposed on a radial cross section of an exemplary embodiment of a fission reactor. For example, the first 6th rotational symmetry 300 is shown between the control rods 200. The second 6th rotational symmetry 310 is shown between the moderators 210 and the 3rd 6th rotational symmetry 320 is a plurality of primary axes in the corresponding cylindrical space 150 for such features. Shown between tubes 160.

Reactor space 108 (and, by expansion, reactor 100) is a ring extending in one or more axial directions as long as the underlying six-fold rotational symmetry is maintained with respect to the longitudinal axis of the reactor space. Note that it can be extended by adding or subtracting related features such as 140 and the primary shaft tube 160 disclosed herein. For example, the radial configuration needs to go geometrically six times, for example 1, 6, 12, 18, 24, 30, 36 rods. This allows each secondary channel containing the fissile nuclear fuel to have the same volume regardless of its location within the reactor space 108, and is uniform between the fissile nuclear fuel, the reactor space material, and the primary coolant. And promotes optimal heat transfer. Thus, for example, a fissionable nuclear fuel composition located at at least some of the plurality of secondary channels forms a set of fissionable nuclear fuel elements that are volumetrically identical throughout the fission reactor. Also, for example, the ratio of the area of the radial cross section of the primary channel to the area of the radial cross section of the secondary channel is constant throughout the fission reactor (one or more primary channels and one or more secondary). Considered with the channel).

Laminated modeling techniques, such as 3D printing techniques that utilize multiple raw materials, can be used to produce integrated and single structures for the fission reactor and fuel loaded reactor spaces disclosed herein. For example, layered modeling technology can create complex shapes and combine them with in-situ sensors, machine vision images, and artificial intelligence to build components based on layer-by-layer layered modeling, allowing for adjustable manufacturing quality. (Often these layers are on a 50 micron scale), providing predictive quality assurance for the manufacture of such reactors and structures.

The laminated molding techniques for manufacturing the integrated and single structures of the fission reactor and fuel loaded reactor space disclosed herein are (a) prediction and causal analysis, (b) layer-by-layer manufacturing of the structure. , In-situ monitoring in combination with machine vision and acceleration processing, (c) automatic analysis in combination with machine learning components, and (d) virtual inspection of the digital representation of the structure at completion (also referred to herein as "digital twins"). ) Includes steps. FIG. 9 summarizes the additive manufacturing method 400 for producing integrated and single structures for fission reactor and fuel loaded reactor spaces disclosed herein.

Method 400 includes predictive and causal analysis 410 that uses existing experimental data to determine early critical quality (CTQ) factors and provides training for early machine learning algorithms. The initial input data for machine learning algorithms can be organically developed, provided by a third party, or with historical datasets (such as open sources and / or potential features associated with the current layered build process). It is either based on operations and experiments that capture the previous experience of laminated molding techniques recorded as observations. In each case, the initial machine learning algorithm is an algorithmic representation of each step of the manufacturing process as well as an ideal final structure algorithmic representation. For example, additional variables such as input, output, manufacturing conditions such as environmental conditions, and supply quality can be included to add more complexity to the initial machine learning algorithm. The algorithms applied to the initial input data provided will help explain the final critical quality (CTQ) factors of the reactor product, but are not sufficient to certify the as-manufactured product. It is expected to be.

Prediction and Causal Analysis The data science methodologies applicable to the steps 410 define (1) defects. (2) Convert to the measured output (layer fusion, shape, position, etc.). (3) A clean dataset that uses the principles of "tidy data" (column variables, row observations, linked tables, test reproducibility). (4) Divide the data into a set of training, testing, and validation. (5) Data set characterization, exploratory analysis, and research into physical theory. (6) Extract the characteristics of the candidates. (7) Describe the hypothesis of the relationship to be tested from existing data. (8) Build a multivariate regression algorithm using a resampling method for randomization. (9) Evaluate the entry and exit of sample errors. (10) Evaluate the hypothesis and establish the basic parameters of the physical test. (11) Create a known laminated modeling geometry, verify the prediction model, and generate causal relationships and output parameters. (12) Reassess the hypothesis and update the basic machine learning-based defect definitions. including. Successful early machine learning algorithms use existing data prior to physical testing to determine basic hypotheses about possible key factors in additive builds and form the basis of machine learning. The final predictive model is then used to inform the in-situ measurement plan for physical production and early machine learning conditions.

The steps of prediction and causal analysis 410 are usually performed prior to the layer-by-layer deposition of material for manufacturing the structure of the manufactured object.

Method 400 includes in-situ monitoring combined with in-manufacturing machine vision and acceleration processing for each layer of structure 420. In this step, proper in-situ monitoring captures data related to the manufacturing of each layer of the structure, accelerates it, and digitizes the data to be input to machine learning for analysis. In-situ monitoring can be performed by any suitable means. For example, industrial machine vision cameras can provide visual information, including location information, thermocouples can provide temperature information for both supplied and as-deposited materials, and current and voltage sensors can provide deposition. Can provide information on conditions, monitor deposition rates and rates, monitor environmental conditions, X-ray technology can not only monitor material properties, but also material characterization, temperature distribution infrared thermography, structure and stress. Weld pool characteristics such as condition can be provided. This is just one example of in-situ monitoring that can be performed and the results can be used in additive manufacturing. Other parameters that can be included in in-situ monitoring include defect detection such as cool-down profile, void detection, porosity measurement, cracks, stacking, and dimensional irregularities. It should be noted that additive manufacturing raises sensor issues. For example, cameras and other sensors need to be placed to collect data between the film layer and the deposition head to detect structural placement and alignment. Parallel processing, such as GPU acceleration, can be beneficial, if not necessary, to process large amounts of data from in-situ monitoring and dozens of functions needed to return real-time corrections. .. The output of the acceleration process is fed back to the machine control in the loop for identification for self-correction or offline analysis using the model at the time of completion.

Continuing to the manufacturing process by repeating in-situ monitoring and automated analysis steps layer by layer as the integrated and single structures of the fission reactor and fuel loaded reactor space disclosed herein are manufactured. Feedback is possible. The feedback is disclosed herein: (i) layer-by-layer adjustments in the stacking process, (ii) digital twin monitoring and archiving of analyzed information, subsequent analysis and evaluation possible, and (iii). It will be the basis for updating and coordinating manufacturing protocols and layer-by-layer instructions for use in future multi-layered and single-structured structures for fission reactors and fuel-loaded reactor spaces.

Method 400 includes automated analysis combined with machine learning component 430 while manufacturing the structure of the manufactured object layer by layer. Machine learning creates intelligence from machine vision and in-situ monitoring inputs, applies that input to existing data, updates processing through machine training, and self-adjusts during the stacking process for predictive eligibility. Perform the analysis.

Machine learning can include anomaly detection algorithms for monitoring process functions. For example, anomaly detection algorithms can check for variations in deposition rate, unexpected delays or volume consumption, temperature, alignment, or chemistry. The automatic analysis of the process data, select one or more features X ₁ indicating an abnormality, by adapting parameters U _1, characterized distribution of each feature selected, the observed X is each feature U The probability of fitting within an acceptable Gaussian error can be calculated.

Machine learning can also include an image classifier for on-going anomaly detection. For example, a pixelated image can be used as input data. In this case, each sample is a small pixel area of the image. The number of areas that fit in an image represents the number of dimensions that can be used to distinguish and classify anomalies and shapes. Vectorized images of hundreds of dimensions (part of the image) allow the machine to learn what the proper shape or anomaly looks like through the optimization features of each feature. When the classifier is trained to detect anomalies, it identifies previously detected deposition conditions (within certain statistical confidence levels) that lead to anomalies and informs them of that information before the anomalies actually occur. It can be applied to field conditions and further trained to actively intervene in the stacking process to avoid anomalies. This iterative correction function is important for in-process adjustment before depositing a large number of defective layers.

Neural networks can be used for nonlinear hypotheses related to machine learning. For example, a neural network uses an array of features that take input conditions and fit the model, use hidden layers to correctly predict output conditions and create weighting parameters. Forward propagation algorithms provide predictive functionality, and backpropagation is used to reveal weighting schemes learned by the system. Hidden layers allow a viable solution to be reached when the number of features is large (such as image data), the interactions are complex, or both.

Method 400 also includes a virtual inspection of the digital representation of the finished structure (also referred to herein as the "digital twin") 440. Typically, the steps of virtual inspection of the digital twin 440 are performed after the completion of layer-by-layer deposition of material for manufacturing the structure of the manufactured object. Digital twins can be analyzed using a variety of computer-aided structural analysis and modeling techniques, such as finite element analysis, to investigate structural analysis, heat transfer, fluid flow, and mass transport properties. Furthermore, the internal features of the completed structure and features that are difficult to access can be easily accessed, displayed, and analyzed with a digital twin. This provides a complete 360 degree inspection and "inside-out" verification capabilities. Since the digital twin duplicates the actual completed structure, the results of such an analysis of the digital twin are highly correlated with the actual completed structure. Therefore, the reliability of the finished product can be statistically evaluated (for the desired parameters such as strength) based on the test results of the digital twin.

In contrast to the myriad of pre-manufacturing, in-manufacturing, and post-manufacturing quality assurance methods of conventional manufacturing, this is often a breakdown-based technology and / or inspection limitation and is disclosed herein. Establishing quality assessments during the manufacture of integrated and single structures of nuclear fission reactors and fuel-loaded reactor spaces not only offsets the difficulty of post-manufacturing verification of complex products, but also manufactures them additionally. It is no longer needed by the more direct guarantee provided by the inside-out assessment of inspecting at the (minimum) resolution of each high resolution layer, returning to the continuous input of process monitoring data along each layer.

In addition, virtual inspections can be performed using models built from finished data that were analytically processed when collected during manufacturing (eg, "digital twins" of physical finished products). The predictive power of the machine to learn anomalies in quality impact (using stored and in-process data) and the status of the final finished product (compared to a continuously updated baseline). Combined with the ability to monitor, interpret, and report, the laminated molding methods disclosed herein not only avoid pre-occurrence defects, but also monitor and record manufacturing conditions during the manufacturing process. Based on this, statistically evaluate the reliability of the finished product's feasibility on a global basis throughout the finished product.

Example 1: A fission reactor sized 16 inches in diameter and 24 inches high was modeled. The reactor has six cylindrical spaces, the axial height of which is divided into 20 equidistant axial levels, 2520 individual primary channels and 2520 individual for potential fuel load. Secondary channel was obtained. FIG. 3A shows the arrangement of features at the axial level from the top perspective view. Dimensional examples of structural considerations include (a) an outer circumference of the shell 102 of 0.75 inches, (b) a primary channel wall thickness of 3 mm, and (c) an axially extending ring and webbing thickness of 2 mm. included. However, smaller dimensions can be used to provide the potential for additional fuel loads, and larger dimensions can be used to provide strength. Below are the volumes of shell metal, primary channel, and secondary channel (uranium metal).

The amount of uranium in Example 1 was calculated. In the above 16 "x24" configuration with a total secondary channel volume (fuel volume) of 1364.3 in ³ , a maximum U235 weight of 187 pounds if all secondary channels are filled with 20% enriched U235. Is possible. However, each chamber incorporates a plenum that allows 10% off-gas content. This resulted in a maximum U235 weight of 149.6 lbs at 20% enrichment. This is well beyond the critically required amount, but this excess capacity allows the enrichment to be adjusted radially and axially to optimize fuel cycle efficiency and cycle length.

The size of the primary channel was arbitrarily chosen to be 18 mm in diameter and 3 mm in wall to balance strength and flow area. As a result, 127 holes with ^{a total flow area of more than 50 in 2 were created.} The number of holes and the size of the flow area can accommodate a huge number of possible flow channels, moderator rods, control rod positions, scrum rod positions, and instrumentation needs. The required power level, liquid selection, deceleration material, control rod material, and concentration drive the specific purpose of each hole.

As can be seen in the drawing, all secondary channels, including fissionable nuclear fuel, eg uranium, are connected to two halves of two different primary channels. Therefore, as long as all other primary channels are dedicated to fluid flow, each secondary channel containing fuel transfers heat to adjacent primary channels for heat transfer purposes. In addition, 60 primary channel positions can be dedicated to non-flow needs (moderator, control, scrum, and instrumentation). Considering the design of the plug, heat transfer in a flow-free position is also possible by not using the entire 18 mm primary channel size. For example, fin-shaped control rod designs can provide reactivity control and proper flow simultaneously in the primary channel.

The example reactor has the advantage of radial and axial enrichment. Each secondary channel that uses fissile nuclear fuel is independent of all other secondary channels that use fissile nuclear fuel, so custom enrichment can be selected in both radial and axial directions. Experience has shown that this improves fuel cycle efficiency by up to 20% and balances shell temperature. It is also conceivable to provide an infinite number of uranium enrichments through laminated molding. For example, the use of only depleted uranium wire and 20% enriched uranium wire in combination allows enrichment between these two extrema (in contrast, conventional practice is that nuclear manufacturers are usually non-concentrated. Limited to less than 10 different enrichments due to the complexity of laminate molding etc.).

The example reactor is expandable and scalable. Modeled with 16 "x24" reactor dimensions, any reactor size greater than 12 "x18" is possible. In addition, the radial width of the chamber is kept in detail within this design, and any number of additional axially extending rings 140 can be added according to the concept of 6-fold radial symmetry described above. The result is a continuous, highly symmetrical configuration with all secondary channels with fissionable nuclear fuel of the same size, regardless of reactor size.

Example 2: Computational platform consisting of ANSYS engineering simulation and 3D design software, SolidWorks solid modeling computer-aided design and computer-aided engineering computer program, and Monte Carlo N particle transport code (“MCNP”) nuclear process simulation program (in this specification). Utilizing and applying the universal reversing reactor computing platform (called "UIRCP"), the ideal thermal configuration of the universal reversing reactor design was solved. Two materials that share the above interface because the fuel and cladding are adjacent to each other in the universal reversal reactor design disclosed herein (see, eg, FIG. 4 and the relevant description herein). Since the coefficient of thermal expansion of is changed, the thermal stress is likely to increase. UIRCP was applied to address this issue, fuel enrichment and reactor shape were repeated to homogenize the radial temperature gradient. Note that due to the nature of linear heat exchange, axial temperature gradients and overall peak temperatures were unavoidable and were not part of the UIRCP process.

The MCNP was applied to a universal reversal reactor design modeled by the UIRCP process, calculating MeV / gram for each adjacent fuel element and checking for criticality. First, the input deck needs to be created based on the user's geometric and material inputs. Other user inputs can include coolant, fuel, cladding, and reflector materials. This is done by reading the user input, outputting the geometry in MCNP format (binary geometry), labeling each cell with the desired material, and setting the neutron physics. The input deck is then executed and the user is given the option to check the geometry at this point using the visualization software features of MCNP. Searching for MCNP output, find MeV / gram associated with each fuel element is converted into W / m ^3, it is stored in a separate file. All these steps are controlled by a management batch file that calls the required commands and subprograms. FIG. 10A shows screenshot 500 of the initial user interface and FIG. 10B shows screenshot 510 of the MCNPX geometry review.

SolidWorks has been applied to the UIRCP process and updated the computer-aided design (CAD) solid model of the reference reactor geometry based on user input. The user input was the selection of the basic geometry. Variables updated by the user were geometry variables: ring spacing, number of rings, clad thickness, passage ID and OD, number of axial segments, and overall height. 11A and 11B show diagrams 600, 610 with the geometric structures and dimensions of the geometrically related variables used in this example. Note the similarities between the geometry of FIGS. 11A-11B and the design of the reactor space 108 of FIGS. 3A-3B.

Using a universal reversing reactor design (such as the designs shown and described with respect to FIGS. 11A-11B) as the basic design, solid models of fuel, cladding, and passages are pre-existing. The UIRCP process opens SolidWorks, runs a subprogram that updates geometry global variables, runs a VBA (Visual Basic for Applications) program to suppress unwanted geometry, and redesigns with new geometry parameters. Call a batch file that builds and stores one-sixth of the core variables. Parasolid 700 (see FIG. 12) is an example of a core parasolid that results from the process. FIGS. 3A-3B containing the core parasolid 700 of FIG. 12, a shell, an axial cylinder, a plurality of axial rings, a plurality of primary tubes, a primary channel, a plurality of webbings, and a plurality of secondary channels. Note the similarities with the design of the reactor space 108 of. The UIRCP process and SolidWorks modeling can change and update the number of rings, passage size, fuel size, overall reactor size, and interstitial cladding to optimize the universal reversal reactor design.

ANSYS has been applied to the UIRCP process to solve the thermo-hydraulic problem of fuel producing heat that warms the coolant flowing through the aisle. Computational fluid dynamics (CFD) tools such as ANSYS FLUENT and structural analysis tools such as finite element analysis (FEA) based on ANSYS Mechanical can be used. Using ANSYS FLUENT and ANSYS Mechanical, the j_script journal was called and core parasolids such as the core parasolid 700 were inserted as a result of the UIRCP process with SolidWorks applied. Next, the ANSYS mechanical was opened to mesh the parasolids to distinguish between solids and fluids. A script has been generated to control FLUENT. The call to the script began by opening FLUENT. The script contains user input references for fuel, cladding, and coolant materials, and has been updated based on these inputs. The mesh interface between the fuel and the cladding was split (this prevents the solid mesh from seeing the interface as a uniform piece, resulting in false results). Coolant inlets and outlets were set to user input speed and ambient temperature. The fuel element was given an appropriate internal calorific value based on the MCNP output. FLUENT then ran a thermo-hydraulic simulation and created a temperature contour map. FIG. 13 is an example of a temperature contour diagram 800 obtained from performing FLUENT, as outlined by the steps above.

The UIRCP process interfaces ANSYS, SolidWorks, and MCNP programs into a single software automation, with individual software iterating towards the final result based on the user's specific optimization techniques. The interface operation was performed by saving the necessary information from the output of one software that waits until it is called while the other software is being automated. For example, SolidWorks and ANSYS programs communicate via solid modeling. After SolidWorks performs a geometry update and saves the parasolid, ANSYS calls the parasolid as the base geometry and performs a hydrothermal analysis. In another example, the MCNP and ANSYS programs communicate via the relationship between fuel enrichment and the radial temperature gradient. During the first iteration, the MCNP performs an initial neutron simulation using the initial fuel enrichment levels of all fuel elements. This corresponds to the internal calorific value (W / m ^{3) for each fuel element.} The internal calorific value is saved and waits for ANSYS to call them. When ANSYS performs a thermo-hydraulic simulation, the radial thermal profile is preserved. The thermal profile informs the MCNP of what the next iterative enrichment will show that the gradient of the radial temperature gradient tends towards zero (if it is the specified optimization technique). This process is repeated until an acceptable level of temperature gradient is reached. It serves as the main iterative loop for the UIRCP process.

Example 3: The neutron engineering of an exemplary embodiment of the fission reactor 100 was investigated. The fission reactor 100 investigated utilized low-enriched uranium (LEU) of 19.75 wt% U-235. The fission reactor had 10 fuel rings located in the reactor space within the shell. The core diameter was 434.7 mm and the core height was 800 mm. A beryllium reflector with a thickness of 15 cm surrounded the core. Neutron engineering was modeled using a Monte Carlo N particle transport code 6 (“MCNP6”) nuclear process simulation program. It was determined that steady state operation (k-eff = 1.0) would require a series of control rod operations over the entire operating life of the core. 14A and 14B show the core power peak profile from the MCNP6 nuclear process simulation program when the control rods are removed from the core. Profile 900 in FIG. 14A shows power (normalized to average) as a function of core height (meters, top to bottom) with a peaking factor of 1.49 (all control rods fully pulled out). It has an axial peaking position at 0.39 m, and a k-effect of 1.06375 ± 0.00036 (control rods are fully pulled out). Profile 910 in FIG. 14B shows power (normalized to average) as a function of radial distance (meters) with a peaking factor of 1.12 (all control rods fully pulled out) at 0.0186 m. It has an axial peaking position and 1.06375 ± 0.00036 k-effect (control rods are fully pulled out). FIG. 14C shows the profile 920 of the neutron flux (normalized to total flux) as a function of neutron energy (MeV) with 1.06375 ± 0.00036 k-effect (all control rods fully pulled). Has been pulled out). For the purpose of shutdown, the k-effect of the modeled reactor with the control rods fully inserted was 0.94211 ± 0.00034.

The UIRCP and the above process give engineers the flexibility to change the type, material, and base shape of the reactor. The end result is a reactor design that can be manufactured using laminated molding technology, providing engineers with tools for a variety of power applications. In addition, the specific functions of the disclosed fission reactors can be optimized through a dedicated routine of the UIRCP process. For example, in addition to the concentration optimization described above, using the UIRCP process, (a) passage size based on one or more of the thermal transfer efficiency of the coolant, the radial temperature gradient, and the axial temperature gradient, (B) For example, the ring width based on the temperature gradient in the radial direction, and (c) the thickness of the cladding tube based on the thermal stress in the radial direction, for example, can be optimized.

In addition, UIRCP and the processes described herein can be effectively applied to the design of new reactors. Engineers are tasked with scrutinizing criticality, thermohydraulics, and material specifications. The design and evaluation of this first project can take months (up to a year) and cost millions to get the first answer on the feasibility of a new reactor design. However, UIRCP and the processes described herein will provide new reactor hydrohydric, neutron, and geometric knowledge in a matter of days. As a result, the usefulness of the reactor design can be pre-determined, saving time and cost compared to current practices and optimizing the design.

The fission reactor 100 of FIG. 2A has baseline characteristics such as 1 MWth (+250 kW) output, ZrH deceleration, helium cooling, Brayton thermodynamic cycle, and rotationally symmetric monolithic. However, the fission reactor 100 can be larger or smaller, i.e., expandable and can have alternative properties as disclosed and described herein.

Fission reactors 100 disclosed herein include, but are limited to, ground power, remote or off-the-grid applications, space power, space propulsion, isotope generation, directional energy applications, commercial power applications, and desalting. Can be used for suitable purposes.

Although generally described herein in relation to pressurized water reactors (PWR reactors) and water as a primary coolant, the structures and methods disclosed herein are boiling water reactors (BWR). Reactors), heavy hydrogen oxide (heavy water) deceleration reactors such as CANDU reactors, light water reactors (LWR reactors), pebble bed type reactors (PBR reactors), nuclear heat propulsion reactors (NTP reactors), It is also applicable to other reactor systems, including both commercial and research reactors, utilizing other primary coolants such as helium, hydrogen, methane, molten salts, and liquid metals.

Although described using laminated molding techniques herein, it is possible to manufacture fission reactors and related structures using subtractive manufacturing techniques, as well as a combination of laminated molding and subtractive manufacturing techniques. can. As such, in-situ techniques and predictive quality assurance methods can be adapted for use in such subtractive manufacturing / combination manufacturing environments. Examples of subtractive manufacturing techniques include machining such as milling and boring, and finishing machining such as electrical discharge machining (EDM) after the body is roughened to a semi-finished shape. Other subtractive manufacturing methods such as electron beam processing (EBM) can be used.

Although described in connection with the manufacture of universal reversing reactors presented and described herein, the laminated molding and predictive quality assurance methods disclosed herein are the petrochemical industry in the aerospace industry. It can be applied to the manufacture of other technologies, including, for example, chemical reaction vessels) (eg, turbine parts including turbine blades and housings, and missile and rocket parts including combustion chambers, nozzles, valves, coolant piping). ).

Although referring to certain embodiments, it is clear that other embodiments and variations can be devised by those skilled in the art without departing from their spirit and scope. The appended claims are intended to be construed as including all such embodiments and equivalent modifications.

Claims (22)

It ’s a fission reactor,
A shell that includes a reactor space with a longitudinal axis,
An axial cylinder containing an inner diameter surface that defines a central longitudinal channel with an axis co-located with the longitudinal axis of the reactor space.
A plurality of axially extending rings arranged in the reactor space and concentrically arranged with respect to the axial cylinder, and the plurality of axially extending rings are separated in the radial direction. For any two adjacent axially extending rings, both a ring adjacent radially inward and a ring adjacent radially outward are formed, and the outer diameter surface of the ring adjacent in the radial direction and the radius. The inner diameter surface of the ring adjacent to the outside in the direction is a ring extending in multiple axial directions, which defines an annular cylindrical space.
A plurality of first primary shaft tubes arranged in the annular cylindrical space in the circumferential direction, and each primary shaft tube includes a first plurality of inner diameter surfaces and outer diameter surfaces forming a primary channel. With the primary shaft tube,
A plurality of webbings, each outer diameter surface of the plurality of primary shaft tubes, is connected to a ring adjacent to the inner side in the radial direction by the first webbing, and to a ring adjacent to the outer side in the radial direction by the second webbing. With multiple webbings connected,
A plurality of secondary channels in a cylindrical space, the primary axial tubes adjacent in the circumferential direction, are separated by one of the plurality of secondary channels.
With a fissionable nuclear fuel composition located in at least some of the plurality of secondary channels,
A fission reactor equipped with. The fissile reactor according to claim 1, wherein the fissile nuclear fuel compositions located in at least some of the plurality of secondary channels form a set of fissile nuclear fuel elements that are volumeally identical throughout the fission reactor. The fission reactor according to claim 1 or 2, wherein the ratio of the area of the radial cross section of the primary channel to the area of the radial cross section of the secondary channel is constant throughout the fission reactor. The inner surface of the secondary channel is a part of the outer diameter surface of the primary shaft tube adjacent in the circumferential direction, and the first webbing and the second webbing related to each of the primary shaft tubes adjacent in the circumferential direction. 13. Nuclear division reactor. The fission reactor according to claim 4, wherein the fissile nuclear fuel composition is in heat transfer contact with the inner surface of the secondary channel. Claim that the primary coolant can flow through each primary channel of a circumferentially adjacent primary shaft tube separated by one of a plurality of secondary channels containing the fissile nuclear fuel composition. The nuclear fission reactor according to any one of 1 to 5. The fission reactor according to claim 1, wherein the primary shaft tubes adjacent to each other in the circumferential direction are non-contactly distributed in an annular cylindrical space. The nuclear fission reactor includes a second plurality of primary shaft tubes arranged in a circumferential direction between the inner diameter surface of the ring extending in the innermost radial direction and the outer diameter surface of the axial cylinder. Each outer diameter surface of the two plurality of primary shaft tubes is connected to the outer diameter surface of the axial cylinder by the first webbing, and is connected to the innermost radial axially extending ring by the second webbing. , The nuclear fission reactor according to any one of claims 1 to 7. The fission reactor includes a third plurality of primary shaft tubes arranged in a circumferential direction between the inner diameter surface of the shell and the outer diameter surface of the ring extending in the outermost radial direction. The outer diameter surface of each of the plurality of primary shaft tubes is connected to the outer diameter surface of the ring extending most radially outward by the first webbing, and is connected to the inner diameter surface of the shell by the second webbing. The nuclear fission reactor according to any one of claims 1 to 8. 1. The fission reactor described. One of claims 1 to 10, wherein the shell, the axial cylinder, the plurality of axially extending rings, the plurality of primary shaft tubes, and the plurality of webbings are formed of a metal alloy. The nuclear fission reactor described in. The fission reactor according to any one of claims 1 to 11, wherein the fission reactor includes a reflector around the outer diameter surface of the shell. The fission reactor according to any one of claims 1 to 12, wherein the moderator, control rods, and scientific instruments comprising at least one are arranged in one or more primary channels. The first plurality of primary shaft tubes in each of the cylindrical spaces has six-fold rotational symmetry with respect to the longitudinal axis of the reactor space, according to any one of claims 1 to 13. Nuclear fission reactor. One or more central longitudinal channels of the axial cylinder and one or more primary shaft tubes are accessible from the outer surface of the fission reactor, any one of claims 1-14. The fission reactor described in the section. The fission reactor according to any one of claims 1 to 15, wherein the primary shaft tube has a longitudinal axis parallel to the axis of the reactor. The fission reactor according to claim 16, wherein the inner diameter surface of the primary shaft tube forming the primary channel changes as a function of the axial position of the primary shaft tube with respect to the longitudinal axis. The fission reactor according to any one of claims 1 to 15, wherein the primary shaft tube is chambered. The fission reactor according to any one of claims 1 to 18, wherein the cross section of the secondary channel perpendicular to the longitudinal axis has the shape of a cross section of one hyperboloid. A method of manufacturing a fission reactor
Steps to apply predictive and causal analysis to prepare a fission reactor model,
Steps to make a fission reactor layer by layer using layered modeling technology,
During production, the steps to monitor the production of a fission reactor with machine vision and acceleration on the spot,
Steps to analyze data from in-situ monitoring and
Steps to coordinate the production of fission reactors based on the analyzed data,
How to include. A method of manufacturing a fission reactor
Steps to apply predictive and causal analysis to prepare a fission reactor model,
Steps to build a fission reactor layer by layer using subtractive manufacturing technology,
During production, the steps to monitor the production of a fission reactor with machine vision and acceleration on the spot,
Steps to analyze data from in-situ monitoring and
Steps to coordinate the production of fission reactors based on the analyzed data,
How to include. The method is
Steps to prepare a digital version of the manufactured fission reactor,
Based on the analysis of the digital version of the manufactured fission reactor, the steps to correlate the characteristics of the manufactured fission reactor and
The method according to claim 20 or 21.

Images